ML20090J005

Monthly Operating Repts for June 1984

ML20090J005
Person / Time
Site:	Browns Ferry
Issue date:	06/30/1984
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8407270348
Download: ML20090J005 (36)

Text

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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PUlNT MONTHLY OPERATING REPORT TO NRC June 1, 1984 - June 30, 1984 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68

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s TABLE OF CONTENTS Operations Summary. . . . . . . . . . . . . . . . . . . . . .

. 1 Refueling Infonmation . . . . . . . . . . . . . . . . . . . . 4 Significant Operational-Instructions... . . . . . . . . . . . 6 Average Daily Unit Power Level. . . . . . . . . . . . . . . . 13 Operating Data Reports. . . . . . . . . . . . . . . . . . . . 16 Unit Shutdowns and Pcwer Reductions . . . . . . . . . . . . . 19 Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . 22 Outage Maintenance & Major Modification . . . . . . . . . . . 29 I

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2 Doerations Si - rv June 1984 The following summary describes the significant operation activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report.

There were six reportable occurrences and no revisions to previous reportable occurrences reported to the NRC during the month of June.

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Unit 1 There were three scrams on the unit during the month. On June 2, 1984, the .

reactor scrammed on turbine control valve fast closure (generator load rejection) when the turbine generator tripped due to generator field ground relay operation. On June 20, 1984, the reactor was manually scrammed when unidentified drywell leakage exceeded the technical specification limits.

The reactor was manually scrammed on June 27, 1984 when a main steam relief ,

valve opened and failed to reseat during startup.

Unit 2

. There was one scram on the , nit during the month. On June 16,1984, the reactor scrammed on turbine stop valve closure when personnel accidentally bumped the low bearing oil tank level switch which ' tripped the main turbine.

Unit '4 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.

Prepared principally by B. L. Porter.  !

. .. . - - - = . -.. -, . . = . . - .

3 Ooerations Sim= mrv (Continued)

June-1984 Fatigue Usage Evaluation-The cumulative usage factors for the reactor vessel are as follows:

Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00609 0.00490 0.00403 Feedwater nozzle 0.29185 0.21218' O.15429 i

Closure studs 0.23676 0.17302 0.13233 .

NOTE: This accumulated monthly infomation satisfies Technical 4

Specification Section 6.6.A.17.B(3) reporting requirements.

Cr-nnn System Approximately 9.04E+05 gallons of waste liquids were discharged containing approximately-2.41E-01 curies of activities. J.

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l Ooerations Su===nv (Continued)

June 1984 Refueline Information Unit 1 Unit 1 is scheduled for its sixth refueling beginning on or about February 8, 1985 with a scheduled restart date of August 27, 1985. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hang 3rs and anchors, and environmentally qualify instrumentations.

There are 764 fuel assemblies in the reactor vessel. The spent fuel stor-

• age pool presently contains 252 EOC-5 fuel assemblies, 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fucl assemblies; and 168 EOC-1 fuel assemblies. The present fuel pool capacity is 3.471 locations.

Unit 2

• Unit 2 is scheduled for its fifth refueling beginning on or about .

September 1,1984 with a scheduled restart date of January 31, 1985. This refueling outage will involve loading additional 8X8R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine 5

inspection, finishing piping inspection, finishing THI-2 modifications; post-accident sampling facility tie-ins, core spray changc-out, and feedwater sparger inspection.-

There are 764 fuel assemblies in the reactor vessel. At the end of the month there were 248 EOC-4 fuel assemblies, 353 EOC-3 fuel assemblies,156 EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent fuel storage i~

pool. The present available capacity of the spent fuel pool is 601 locations.

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. Operations Surunary (Continued)

, June 1984 Unit ~4 Unit 3 shutdown for its fifth refueling outage on September 7, 1983, with

,a' scheduled restart date of September 1, 1984. This refueling involves load-

, ing8X8R(retrofit)assembliesinto$hecore,finishingthetorusmodifica-tions, postaccident sampling facility tie-in, core spray change-out, finishing THI.- 2 'r.odifications, turbine inspection, piping inspections for cracks, and r charigeout of jet pump hold-down beams.

Therearebfuelassembliespresentlyinthereactorvessel. There are 248 new fuel assemblies, 764 EOC-5 fuel assemblies, 280 EOC-4 fuel assemblies,

.124 E00-3 fuel assemblies,144 E00-2 fuel assemblies, and 208 EOC-1 fuel assemblies in the spen *, fuel storage pool. The present available capacity of the spent fuel" pool is 150 locations.

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Sinnificant Operational Events

- Date Time Event -

, Unit 1 t

6/1 0001 Reactor thermal power at 100-percent (%), maximum flow, rod-limited.

0925 Commenced reducing themal power for control rod pattern  ;

adjustment. i 1000 Reactor thermal power at 85% for control rod pattern adjustment. ,

1150' Control rod pattern adjustment complete, commenced

.PCIOMR from 85% power.

1500 Reactor thermal power at 89%, holding up on PCIOMR for

. flux shaping.

1611 Increased thermal' power to 90% for f]ux shaping.

Reduced thernal power to 895 for flux shaping.

1630 1647 Reduced thermal- power to 88% for flux shaping.

, 2335 Reactor thermal power at 88% for turbine control valve test and sis.

6/2 0145 Turbine control valve test and sis. complete, commenced PCIOMR from 88% thermal power.

1100 Reactor thermal power at 1001, maximum flow, rod limited.

i 1739 Reactor Scram No.173 from 100% thermal power' on TCV fast closure (generator load rejection) when the turbine -

generator tripped due to generator field ground relay

, -(64GF) operation. This was caused by the plate-out or crud b:aldup of solids on the excitation. rectifiers cooling water isolator tubes'from the stator. cooling ,

water.

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6/3 :1000 Commenced rod withdrawal for startup.

1357 Reactor Critical No.'.196.

, 1830 Rolled Turbine / Generator.(T/G).

1900 Synchronized generator, commenced power ascension.

l 6/4. 1430 Commenced PCIOMR from 85% thermal power.

6/5' -1415 Stopped PCIOMR at 935 due-to: generator. rectifier problens. ~

2300 Reactor thermal power'at"92%, generator rectifier

. limited.

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7 Significarat Ooerational Events Date Time Event Unit 1 (Continued) 6/6 0700 Reactor thermal power at 915, generator rectifier limited.

0900 Comenced power ascension from 91% power.

1000 Comenced PCICHR from 92% thermal power.

2100 Commenced reducing thermal power from 95% due to recirculation pump "A" seal leakage annunciation.

6/7 0100 Reactor thermal power at 91% for investigation of "A" recirculation pump seal leakage annunciation.

0953 Reduced thermal power to 90%, "A" recirculation pump seal leakage annunciator limited.

0954 Comenced power ascension from 90% thermal power.

• 1005 Reactor power at 91%, "A" recirculatior pump seal

. leakage annunciator limited.

i 1545 Comenced PCIOMR from 91% thermal power.

i 1950 Reactor thermal p wer at 955, maximum flow, rod limited.

6/8 1500 Reactor thermal power at 97%, maximum flow, rod limited.

2106 Comenced reducing thermal power for control rod pattern adjustment. ,

2134 Reactor pcwer at 73% for control rod pattern adjustment. -

2200 Control rod pattern adjustment complete, comenced power ascension.

2300 Reactor thermal power at 75%, holding for turbine control valve test and sis.

6/9 0100 Turbine control valve test and sis complete, commenced power ascension.

0730 Commenced PCIOMR from 925 themal power.

1310 Stopped PCIOMR at 99%, computer out-of-service.

1400 . Reactor power at 98%, computer limited.

1650 Comenced PCIOMR from 985 thermal power.

2100 Reactor thermal power at 100%, maximum flow, rod limited.

6/10 0800 Reactor thermal power at 995, maximum flow, rod limited.

1620 Commenced reducing thermal power for SI 4 3.A.2 (Control

' Rod Exercise).

1700 . Reactor power at 96% for SI 4.3.A.2.

1730 SI.4 3.A.2 complete, commenced PCIOMR.

2130 Reactor thermal power at .100%, maximm flow, rod l Limited.

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8 Sicnificant Ooerational Event.g Date Time Event Unit 1 (Continued) 6/11 0937 Recirculation pump "B" tripped, reducing thermal power.

1300 Reactor thermal power at 62%, recirculation pump "B" limited.

1335 Recirculation pump "B" back in service, commenced power ascension.

1700 Commenced PCIOMR from 98% thermal power.

1800 Reactor thermal power at 100%, maximum flow, rod limited.

6/16 2300 Commenced reducing thermal power for control rod pattern adjustment.

2333 Reactor thermal power at 68% for control rod pattern '

adjustment. ,

6/17 0200 Increasing thermal power for control rod pattern adjustment.

0230 Control rod pattern adjustment complete, holding at 89%

thermal power for turbine control valve test and sis.

0505 Turbine control valve test and sis complete, commenced power ascension.

0520 Reactor thermal power at 100%, maximum flow, rod limited.-

6/18 1500 Reactor thermal power at 995, maximum flow, rod limited.'

6/19 0700 Reactor thermal power at 100%, maximum flow, rod limited.

2250 Commenced reducing thenmal power for shutdown due to excessive leakage into drywell floor drain.

'6/20 0050 . Reactor manual Scram No. 174 from 59% thermal power to determine' source of leakage into drywell floor drains (later detennined to be ."B" recirculation pump seal).

The unit remains down for repair of the seal and for a short-maintenance outage.

1315 Unit in cold shutdown.

6r21 2230 "

B" string low-pressure heaters tagged out for-maintenance.

16/22 0400 "A" bank of drywell blowers tagged out for maintenance.

1900 "B" string low-pressure heater maintenance complete.

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Sinnificant Goerational Events Date Time- ~ - - -

- Event- -- -

Unit 1 (Continued) 6/23 0200 Maintenance complete on "A" bank of drywell blowers.

6/25 1046 Maintenance and testing complete on "B" recirculation pump.

6/27 0010 Commenced rod withdrawal for startup.

0230 Reactor Critical No.197.

0557 Main Steam Relief Valve (MSRV) 1-4 opened.

0608 Reactor Manual 3 cram No.175 from 1% thermal power for replacement of MSRV 1-4.

1400 Reactor in cold shutdown. .

6/28 1538 Maintenance complete on MSRV 1-4. ,

1637 Shutdown cooling out-of-service and valves lined up for local leak rate test on FCV 74-48.

1925 Local leak rate test on FCV 74-48 complete.

2110 FCV 74-48 and shutdown cooling back in service.

6/29 0625 Cormenced rod withdrawal for startup.

0821 Reactor Critical No. 198.

1315 SI 4.6.D-2 performed on MSRV 1-4.

1750 Reactor pressure at 100 psi, holding for drywell entry n-to inspect MSRV 1-4. Reactor thermal power at 5%.

1940 MSRV 1-4 inspection _complate, valve checked out okay.

2020 Comnenced rod withdrawal from 5% thermal power.

2250 Rolled T/G.

2355 Synchronized generator, commenced power ascension from 22% thermal power.

6/30 0700 Reactor thermal power at 63%, startup sis in progress, decreasing thermal power.

1800 Startup sis comp 1'te, commenced. power ascension from 54%

i thermal power.

2400 Reactor thermal power at 86% power ascension in progress.

10 Sienificant Operational Events Date T192_ Event ~ ~ -

Unit 2 6/1 0001 Reactor thermal power at 60% to extend fuel cycle and administrative hold because all ADS relief valve cables are routed through the same cable tray.

5/12 0700 Reactor thermal power at 61% to extend fuel cycle and administrative hold.

6/16 0027 Reactor Scram No. 152 from 61% thermal power on turbine stop valve closure when an Auxiliary Unit Operator accidentally bumped the low bearing oil tank level switch which tripped the main turbine.

0645 Commenced rod withdrawal for startup.

1022 Reactor Critical No. 162, 1530 Rolled T/G.

1600 Synchronized generator, commenced power ascension.

6/17 0440 Reactor thermal power at 60% to extend fuel cycle and administrative hold.

1500 Reactor thermal power at 58% to extend fuel cycle and administrative hold.

2300 Reactor thermal power at 57% to extend fuel cycle and .

administrative hold.

6/18 0700 Reactor thermal power at 56% to extend fuel cycle and administrative hold.

0835 Increasing thermal power to 60%.

0900 Reactor thermal power at 60% to extend fuel cycle and administrative hold.

6/23 0700 Reactor thermal power at 59% to extend fuel cycle and administrative hold.

6/25 1500' Reactor thermal power at 60% to extend fuel cycle and administrative hold.

6/ 26 2300 Reactor thermal power at 59% to extend fuel cycle and administrative hold. .

6/28 0001 Reactor thermal power at 60% to extend fuel cycle and administrative hold.

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11 Significant Operational Events Date Time - - -- -- -

Event - - -

Unit 2 (Continued) 6/30 0815 Inserted control rod 38-47 for maintenance on accumulator, reduced thermal power to 58%.

1809 Maintenance complete on control rod 38-47 accumulator, withdrew control rod and cournenced power ascension.

1830 Reactor thermal power at 60% to extend fuel cycle and administrative control.-

2400 Reactor thermal power at 60% to extend fuel cycle and administrative control.

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. 12 Significant Ooerational Events Date - - Time - - - - - - - -

Event -- -- - -

Unit 3 6/1 0001 End-of-cycle 5 refuel outage continues.

6/30 _ 2400 End-of-cycle 5 refuel outage continues.

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13 4VER AGE D AILY UNII POWER LEVEL

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DOCKET NO. _50-259 UNIT Browns Ferry-1 DATE 7-1-84 ,

Ted Thom C0\lPLETED BY

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TELEPHONE 205/729-0834 MONTil June 1984 DAY AVERAGE DAILY POWER LEVEL DLY AVER AGE DAILY POWER I.EVEL

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" U I 988 17 992

, 753 g3 1052 81 3 1040 39

• 4 810 20 12 s 962

,  ; -13 983

-15 976-7

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-12 M 981 9 1003 25 -12 -

la 1055 '

26 -14 gg 960 y, -11 12 1057 28 -11 g3 1055 3

'9 -12' g4 1058 30

- 548-15 1057 16 1023 INS TRUCTIONS i

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Ilit* fitJtest Ilit the u hole ncpwatt. aerace aair> u,,ii powe, iesei ti, uwe.mi ro, caesi a23 ii ihs. repo,iirig i, ion h. c

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DM'KET .N o. 50-260-UNIT Browns Ferry-2 DATE __7-1-84 CO\fPLE1ED gy __Ted Thom TELEPlf0NE _205/729-0834 MONili June'I984 UAY

- AVEHAGE D tity powrg ggyp,~

- (\fWe Net) DAY

-\VERAt E DAILyPOWER LEVEL 3 --

595 (%fwe Neg 2- 604

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I7 - -552 3 _

601

-Is _

567

,, 604 19 __

591

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592 __

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594 28 -- . . . _ _

590

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9 600 24' ----- 581 10 25 587 -

-__ 601 26 585-II 594

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606 23 579 3

9 591 la .-

604

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15. _ 602 _

16 107 - I _

- INSIMUCilONS On this fonna, int :

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i- .' 15 SVER AGL DTILY ( sty p0hER LEVEL DOCKET NO. 50-296 UNIT Browns Ferry-3 DATE 7/1/84 .

COMPLETED BY Ted Thom TELEPilONE 205/729-0834 MONitt June 1984 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL

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4 -5 20 -5  %

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9 -5 25

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INSTRUCTIONS

-- tii n at I i$lt r g P"*' '*8 I" M"#'N#' f 't each if 43 i i it,e reg,.,,,i,,g ,,,,,risti. C...im n.

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16 OPER A !!NG DA TA REPORT DOCKETNO. 50-259 D\TE 7/1/84 CO\1PLETEU liy Tgd Thom -

11.1 f PilONE 205/729-0834 OPERVIING S I \ lCs

1. Unit Name: Browns Ferry - One N"'"'

2. Reporting PeriuJ. June 1984 3.1.icenwd I hennal Pow er iSth e n: 3293 4, Nameplate Raling (Grow \1Wel 1152

5. Doign Electrical Rating aNc .\tWe : 1065 ti. $lasimum Depemlable Cap city (Grow StWel: 1098.4

7. Siasimum Dependahic rapacity (Nc .\twe,. 1065

h. If( hango th sur in Cap.' .city Ratings illems Number 3 t hrough 7 Smer t nt Rep.ne. Giac Re. nun.

N/A

' 9. Power 1.cirl lu w hich Rntracted. II .\n3 (Net \1hes. . N/A _

10. Reasons for Rntrictions. it \n3 : N/A thidfunth Yr. te.-Date Cumulative

.11. Ilours in Reportmg preind 720 4,367 86,929*

12. Number of fl.mrs Reactor ha, critical - 479.82 3,885.10 53,691.22 <

13. Reactar Hrvne Shutd. un llour, 240.18 465.58 6,250.60 14 linues Generator On-l.inc 455.57 3_,764.95 52,482.59

15. l' nit Rrwne Shutdown 11o9,, _0 0 0 it Grow thermal Energs GeneraicJ t\1Wils 1,392,881 .I1.312,995 149,870,674 17 Grow Electrical Energy Generated i Albill 455,600 - 3,788,190 49,433,810 IN. Net Electrical Energy Generated t.\lWH) 440,337 3,688,762 48,014,089

19. Unit Senice factor 63.3 86.2' 60.4

20. Unit .uailability facto, _63.3 86.2 60.4

21. Unit Cagueir3 ractor IUsing .\lDC Net 57.4 79.3 31.9 22 Unit Caparity Factor (Using DER Neil - 57.4 79.3 51.9

' 23. Unis Turced Outage Rate -36.7 .13.I 23.1

'24. Shutdow ns S-heduled Oscr Ness ti 3lonth t 13 pc. Danc.and Duratina ni i achi

25. If Shus Down \t I:nd Of Report Period. Estimated Darc ol' Startup:

-2ti. Units in in Status ePrior io Commercial Operation rurrea t .\chiesed INill \ L CHillC.\ Lil y INi ll \ l. f t.l-C I Riril y CO\l\ll'Rrl \1 Opl R g IlON Pr/'73 s _;i,, e

17 OPERA TING DATA REPORT DOCALISO 50-260 la g il; 7/1/84 C O\lPl.i.11 O liY Ind Thod I i 1.EPilON E .205/.7194)83'.

OPI R A IlNG Si \ IUS

1. Unis Name; Browns Ferry - Two h"'"'

2. Reporting Period: June 1984 3.1.icenwd I hermal Power 1%Ihip. '1293

4. Nameplanc Rating IGrow Alwel. I152

5. Design Electrical Rating iNc 31Wel: 1065 ti. Stadmum Deiwndable Capacity aGrow Sthep 1098.4

- 7. %Iasimum Dependahic Capacity #Nc AlWel: 1065 M. If( hanges Occur in Capacits Ratings tirems Number 4 ihrough 76 Since 1.ast Report. Gi c Reaums

+

N/A

9. Pourt Lesci lu which Restricted,Il Any gNc .stwc,. N/A ,

10 Reasons I or Resirictions. Ir Any: N/A

'Ihis stone. yr..ro.D ic Cn,nul.erisc

.11. Ilours in Reporting Period 720 4,367 81,870, l'2. Number Of Itours Re:ector hIn Critical _710.08 4,066.92 54,031.10

13. Reactor Mcwnt Shutdown llours -9.92_ 300.08 14.200.44

14. Ifoun Generator On Line 704.45- _4,016.59 52,509.43

15. Unie Rcwnc Shutdow n llou,, 0 0 0

16. Grow Ihermal Energy Generated I.\lhill _1,382,462 9,326,074 149,471,119

17. Grow Electrical Energy Generated istwill 4._28,260 3,0,02,890 49,600.I'8

18. Nc Electrical Energy Generated s.\th Hl 4 14,159 2,919,529 48,178,132

19. Unit Sen. ice factor E8 - 92.0 64.1.

20. Unir Ausil.ibihty factor 97.. 8 92.0 64.1

- 21. Unit Ca;uciti ractor iUsing.\tl>C Nc0 '54.0

- 62.8 55.3-22 thiit Calucity factor tUdng 181:R Neil 54.0 62.8 5;.3

23. Unit forced Ourage Rate 2.2 _

5.8 23.6 24.- Shutdowns Scheduled Oscr Ned ti slonths. 1) pc. D.nc. and Duration'of I ach t AuguSL 1984 - Refuci 25..~ ll Shul llow n TI End Oi Report Period. Lstimated Date it Siartup.

2e,. ~ Units in less Stains iPrior to Commercial Opciation t forecast - Achis *cd INilI si. CHillCal 11 Y INI18\1.1.1.1ClRICIIY

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18 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 7/1/84 CO31PLETED BY Tori Thnm TELEPflONE 205/729-0834 OPERATING STATUS

1. Unit Name: Browns Ferry - Three b"

2. Reporting Period: June 1984

3. Licensed Thennal Power 1 A1% t1: 3293

4. Nameplate Rating IGross MWe): 1152

5. Design Electrical Rating (Net alWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Maximum Dependable capacity (Net MWe): 1065 M. If Changes Occur ir Capacity Ratings litems Number 3 Through 7) Since Last Report.Give Reasons:

N/A

9. Power Lesellu Which Restricted.lf Any INet MWe): N/A

10. Reawns For Restrictions. lf Any: N/A -

This Month Yr. to Date Cumulative i1. linurs in Reporting Period 720 4,367 64,295

12. Number OfIlours Reactor was Critical 0 0 43,087.80

13. Reactor Resene Shutdown flour, 0 0 3,878.13

14. linurs Generator On-Line 0 0 42,193.71

15. Unit Resene Shutdown flours 0 0 0

16. Gross Thermal Energy Generated (MWil) 0 0 126,307,711 .

17 Gross Electrical Energy Generated (MWH) 0__

0 0 R j97.620

18. Net Electrical Energy Generateo s WH) 0 0

40.375.256

19. Unit Senice Factor 0 65.6

20. Unit Asailability Factor 0 0 65.6

21. Unit Capacity Factor IUsing MDC Neti 0 0 59.0-

22. Unit Capacity Factor IUsing DER Net) 0 0 - 59,o

23. Unit Forced Outage Rate 16.-4

24. Shutdowns Scheduled Oser Nest 6 Months IT.s pc. Date and Duration of Eacht:

25. If Shut Down At End Of Reimrt Period. Estimated Date of Startup: Auguce 14R6 .

26. Units in Test Status IPrior to Commercial Operation 1: Forceast - Achiesed INITIAL CRITICALITY INITIA1. ELECTRICITY j COMMfRCIAL OPERATION l

l 19/77) l

. --+

DOCKET NO. 50-259 UNIT SilUTDOWNS AND POWER REDUCTIONS "

UNIT NAME Browns Ferry-1 +-

DATE 7/1/84 REPORT MON nt June 1984 COMPLETED BY Tod Thom IELEPHONE 205/729-0834 h DJte jg 3 j E5 luemce  ;= -r., h, cause A curvestise

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25$ l.sent y? {? Attson to fE 4 5i; Rep.n t = zL ,E -

Presen Returrente d

282 6/2/84 F 25.35 A 3 Reactor scram on TCV fast closure (generator load rejection).

283 6/,8/84 S H Derated for control rod pattern adjustment 284 6/11/84 F A Recirculation pump "B" tripped 5 z85 6/16/84 S 11 Derated for control rod pattern adjustment 286 6/20/84 F 173.27 A 1 Reactor scram to determine source of leakage into drywell 287 6/27/84 F 65.78 A 1 Reactor scram for replacement of MSRV l-4 I 2 1 4

F: Forced Reason: Method:

5: Scheduled ISlubit G - Inst ructio.n A.Equipmem Failure (Explain) ,

I Manual t'os Piep.u.iin>n ot I).iu B Maintenance of Test 2 Manual Seram.

' I:ntn Shecis for I.neensee C-Refueling .LAutom.itie Stram. I sent Rep n a1.l'Ri File NI RI r.

D Regulatory Restriction 4 Other II:splami 01:41i E-Operator Training & Litense F.umination F-Administrative 5 G. Operational Euros (Explain t 08/77) liother (Explain) Estubit I Same Soura 0

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-260 UNIT NAME Br wns Ferry-2 '.

DATE 7-1-84 REPOR T MONTN June 1984 COMPLETED BY Ted Thom TELEPHONE 205/729-0834 I

_? E No. Date

, .5 ? 3 j 5'i Licensee ,E-r, E *, Cause A Correctise i 3? 4 .3 s E Event a7 E? Astion to

-2: :E 3. f, =! Report = Elb O

E' Prevent Recurrence L

'293 6/1/84 S 11 Derated to extend fuel cycle and ad-ministrative hold because all ADS

' relief valve cables are routed through the same cable tray.

294 6/16/84 F 15.55 G 3 Reactor scram on turbine stop valve w closure - AUG bumped' low bearing oil tank level switch.

295 6/17/84 S H Derated to extend fuel cycle and ad-ministrative hold because all ADS relief valve cables are routed througl i the same cable tray.

I 2 3 4 F: Forced . Reason: Method:

. S Ssheduled A Equipment Failure (Explain) Inhibit G Instrucinios t Manual for Preparainin of Data B Maintenance of Test 2-Manual Seram.

E.or,s Sheets Ior Licensee C-Refueling 3 Automatic Scram. ,

D-Regulatory Restriction Event Report iI 1:R) File iNURI.G-  !

4-Other (Explain i 0161i L-Operator Training & License lhanunation F. Administrative 5

G. Operational Error (Explain t 49/77) Il-Ot her (E xplain) rsinbn 1 Same Source  ;

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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-296 ,

UNIT NAME srowns Ferry-3 DATE 7/1/64 REPORT MONilt June 1984 COMPLETED BY Ted Thom TELEPtf0NE 205/729-0834

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c: x wi: Repor t 20 EC j d Present Recurrente 140 6/1/84 S 720 C 4 End-of-cycic 5 refueling outage con-tinues (controlled shutdown 9/7/83) t to e-a I ~

F: Forced 4

Reason: h S: Sched ulcil A. Equipment Failure (1:xplaint f.3,,j g' Eshibit G - Instincti. i, H. Maintenance of Tes f'os Psep.st.ituin i.: D.n.,

~, '" "'I b,# ' ' " -

C Refueling Ents) Sheets s'on Ixen ,.e D Regulatory Restriction ", ,',",'! j [' ',',',','" - 1%ent Rep..ri s l.I' R i rite i NI;RI r..

iH ol l I -Operator Training A Litense INanii,,,,,i,,n F-Administeative 5

G-Operational Er ror (Esplain1

- i9/77) llother (Explain) IThibit I Sanne Sousee

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CSSC E0tfIPME';T '

ELECTRICAL MA!!;TE!;A! ICE SDS1ARY ' Appendix B-9/29/82 r . '.

For the ." nth of June

. 19 84 .

U

]. Effeet va safe

~

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?.sitare of . Operetion of Caus..O*- Re.sults e.f j'Dat- Svsten C% >o n.:a t L in t en.in ce The Roactor Malfunction, 'talfunction To l're F fe

1984 b ete r r or . ,. _

High-Pres- 0-FMP-26-00B I Replace bearings None'

'- 6 / 22 sure fire -

Excessive vear Excessive vibration' Replaced bad bear-and oil

, Protection in3s

-f . MR (8141789 l6/16 Stand-by 0-GEN-82-00B' ' Troubleshoot None 3 rounded test diesel. Diesel would not stop Removed grounded equipment on command oscillograph and generator-

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l ground cleared

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CSSC EQUIPMENT; ELECTRICAL MAINTENANCE ' SC: MARY 9/29/82 For he Man:5 of June *19 84

-Effeet oa Safe.. Act ion Ta-: en Lture of . ~ Operatinn of Caus..af

Da R .- Svstem Ca.m;ionen t ' .'* tin enance The Reactor Ke.,o!ts'of To Prec ! rie ji'

1983' Malfunctian Malfuncrian Fecurro ,w-1/6' Neutron ~ 1-LPRM-92 Replace None Bad connectors

~

,41C,32-09D, Inoperable LPRM Replaced bad l connectors. cables '

' monitoring!3217C 24-17C.:

connectors32-49D MR #203129 1984 Unit pre- 'l-00-252-00 l Replace. switch- None j Bad switch-lAbnormalalarm Replaced bad switch-

-3/13 .ferred120!switchvolt-voltmeter ' voltmeter will not clear voltmeter lVACf- ' meter MR #267850 ,

4/4 .jRHR l 1-FCV-74-48 ' Record motor None None None. Followup testing'to

'= .

voltage and LER 259-84012 cu m nt 1

MR #252075 U$ l i

4/18 ' Reac tor. 1-SI-68-71 j Replace tach- None Bad tachometer. lSI-68-71 reading Replaced had water-lometer down scale tachometer recirc.ula-  !

tion :i l MR 267298-9 l

~4/20 I&C 1-XFA-253-A Bypass regula- None JUnbalanced load Load I&C voltage 120VAC ting trans -

Replaced regulating 3 -

former transformer and monitored voltage ,

I l MRs 254777, 252078, l252076, 252077

~

l < .' ,  ;

5/3. l Reactor-- 1-CLN-70-144 Replace motor. iBent shaft Breaker for A-4 cool- Replaced bad motor,

-' building wheelassemblylNone ,

l er tripped af ter { wheel assembly closed and solenoid l-cooling:

'. f l l10sec. 'and solenoid water l l MR d268519 ,

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CSSC EQUIPMENT. "

ELECTRICAL MAINTENANCE SDetARY 9/29/82 -

For the Panth af June

• 19 84 i

F i

Effect on Safe Action ; e en p

'ature of

. . Operatton ot Cau.w .of Sy .- t e : ' ;.-

.Co :;'ioncnt To. Pre Dole D.n . . Resial ti cf

. Pa ir.t e na n c e T_ne Reartor Malfunction

n 1984 I- Malfunction Recurren..-

~~~

6/6 . Air-con- 1-CHR-31-0013 Replace'com- None Wear tioning)

Chiller will not run Replaced bad com-pressor , pressor

. .t.

l MR #265384 i l .

6/13 a f

1-RLY-57-83 ' Replace relay None: LBad coil iBreaker tripping Replaced bad relay jtransferringloadto f *

[ galternate source MR #256195-f 6/22 iRHR- 1-LA-23-80A ' Replace level None i Bad level switch

,(service '

switch Level switch indicat- Replaced bad level-I ing false level

'"#E"# switch i

l-i MR 265985 s 6/25 'RPS 1-RLY-99-5AK5D Replace relay None Bad coil Relay smoking Replaced bad coil coil

. MR #267439-i

'6/23 -8.RB closed FSV-70-85. Replace sole-

• None  ; Bad coil

. l' cooling Damper-will not oper- Replaced bad sole-noid coil .

ate noid coll

~l water? ,

I MR 254468 6/23 Diesel 162-SW-254-00D Replace speed None l Bad switch 125VDC switch fpcedswitchcontactslReplacedbadspeed w

,ill not seal in  ! switch jMR #254472

~

1. ,

.6/26  ;: Main 1-FCV-1-55 Replace coil jNone jBadcoil .FCV will not operate  : Replaced bad coil

.[ steam

lMR267386 l

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CSSC EQtrIPMENT- -

' . ELECTRICAL MAINTENANCE SL?tMARY 9/29/92 Dr t!n t' " t h of June 19 84

-I :r;-

i

, Effect;an Sa:e N.sture af .

Oper.itfaa of .k: ion T C:en Date Sydtem C =ponent' Cau.se .0f Kemilti of Te Prc. li:.!c -

M.t in t en.a nc e The Re.ic t o r 1984- t 6 Malfunctian  ? tai:unct f an 'Fecurror.+r

.5/31 .heactor. 2-LA-70-2A. Replace card None' Bad card Building-RBCCW surge tank Replaced bad PC high level alarm card

. Closed jCooling. . l MR #252859 6/9 5 Radiation-I 2-RM-90-249 IReplace motor None Bad. bearings CAM motor noisy Monitoring Replaced bad mo. tor-

.. MR #265452 t i 16/13' Meacto- i'-FCO-64-5A Replace motor None  : Bad motor Building

~

Motor.will.not close. Replaced ~ bad motor

~- t damper-HVAC JfR #14l_709 w vs r

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~ CSSC ' EQL*!!"'ENT ELECTR ICAI." MAINTENANCE : St?: MARY 9/29/82' a*

Fr-.tbe P : th o f- June'

• 19 84 .

' Pffect va S.ife .h t s.n.

4. .en; .

. .'.a t u r e ' o f Ope rat i.m i.: C;i n.. .a-' He,a't  ::

9. s sv.,tre Cc.penent- ' Th P r.. -c ,

M.s i n t en.mco The Ecactor Malfunction 5:a t:'u n e 1. m F.curr 1984' i

'~~~~

4kV shut-~ l

^ 2/15 3-RLY--211 . Replace coil None' .None None. , Replaced w:t h new

..I CASA-1

.down ... , ,

jtype coil b rds ;l' iMR.#202391 tref.

j. .l * + ' I;MI' .40)

I 3-RLY-82-CRA l3/8i Standbyf Replace relay None Cracked coil- None Replaced ba : relay

. diesel. I

• generator MR #254752'(ref..

i. ,.lL s i

j SEMI - 37);

.38 /  : Standby. [ 3-RLY-82-VSRD Replace relay l-None. 3 None Replaced _ bad.-rela;.I '

diesel

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I lCrackedcoil

. f '

' generator MR #254756-(ref.

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SEMI 37) i i4/30 RHR- 3-MVPO-74-0060 Replace torque 'lNone- l Broken torque j None ' Replaced broken-switch .j switch F torque. switch

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. .iMR #254296 os e

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[3/7l.

Replace cable 'lNone f

• HPCI- 3-LS-73-5 Bad / broken iLevel switch Replaced bad <

l  ! inoperable . cable 3E52655-II 1 cable I

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lMR #202323

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7' BROWNS FERRY NUCLEAR PLANT UNIT 2 CSSC EOUIPMENT MECHANICAL MAINTENANCE

SUMMARY

For the Month of June 19 84 EFFECT ON SAFE ACTION TAKEN

'DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESUI.TS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTICA MALFUNCTION RECURRENCE 6-1 Reactor. Core Isolation 2-TRB-71-009 Drained oil, cleaned None Routine Matr.;.cnance N/A N/A Cooling (71) filter.and added new oil.

l

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BROWNS FERRY NUCLEAR PLANT UNIT 3

~ CSSC EQUIPMENT MECHANICAL FJINTENANCE

SUMMARY

For the. Month of June 19 84 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NARJRE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTIJANCE THE REACTOR MA1 FUNCTION MALFUNCTION RECURRENCE 6 ;l Standby Diesel Generator 3-DG-82-373 Annual inspection None N/A N/A N/A

-(82) on diesel generatc r 3B 6 Diesel Starting Air 3-DG-86-003C Annual inspection None N/A 1A N/A (86) on diesel generatc r 3C

' 6-5 Standby Diesel . 3-DG-82-003A Annual inspection None N/A N/A N/A Generator (82) on diesel generator 3A w co 6-8 Standby Diesel 3-00-82-0000 Move pressure None N/A N/A This was to Generator (82) sensor to bottom resolve a connection NRC concern 6-8 High Pressure Fire 3-VLV-26-0087 Disassemble, clean None Normal age & use Valve leaking MR A-251922 Protection:(26) and reassembic thru Magnetic by pass valve

• e I  ! .

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. OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT JUNE 1984 I. Work Synoosis The unit 3 end-of-cycle 5 refueling outage schedule progressed through day number 298 (of 351) by the end of the June report period. Major preplanned work items include P0392 CRD Scram Discharge Header Modification (Electrical and Mechanical), and P0399 Instrument and Control Bus Modification (providing long-term solution to instrument and control' bus problems including a related ECN P5097 to install a 10KVA regulating transformer). A major emergent work item was' identified in the need for jet pump nozzle weld ~ overlay which necessitated vessel draindown. This additional work had a significant duration effect on the overall outage duration. The following is a summary of the major events during this work i

period.

A. Critical Path Activities

1. Jet Pump Nozzle Repair Reactor Vessel Draindown - Reactor cavity was drained on June.16 after special procedures were approved. All preparations for continuing the draindown into the vessel were completed on June 22 at which time the draindown was resumed.

Draindown was complete at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on June 24, 1984. The manual welding on nozzles N8A and.N8B was started at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> and completed at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on June 24. The automatic welding of the reinforcement i

weld was then started. At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> on June 27, the automatic 4

welding process' was completed on the base metal layer and the vessel

~

.refil1 was begun.. The weld overlay process was continued in parallel'

~

with vessel / cavity refill'and was approximately 90-percent complete at' the end of the June report period.

= . t. . . . 2- -- -

,, ,,- _4 . - -

c 30 ,

OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT JUNE 1984 A. Critical Path Activities (Continued)

~

2. P0399 Instrument and Contrel Bus Modification -- All cable termina-tions complete that are necessary prior to bus outages. Awaiting bus outages to continue work.

3. P5097 Install 10 KVA Regulating Transformer to Support P0399 --

Completed core drilling through P-line wall. Presently installing conduit on P-line wall. Work is 40-percent complete.

4. P0392 CRD Scram Discharge Header (Mechanical) -- Work is continuing on the rerouting of H 0 and nitrogen purge lines. Continuing efforts on 22 support hangers, lacking 6 of 119 hangers being complete.

5. P0392 (Electrical) -- Work is continuing on conduit and junction box hangers. Design and installation method problems are delaying timely completion of work in the spreader room. -

6. Main Steam Isolation Valves (MSIVs) -- All valves have been reassembled. Work is being held up pending receipt of five additional -

1-7/8" bonnet' nuts.-

B. Refuel Floor Sheave bushings were replaced on the overhead crane. This work was started-on June 3 and completed on June 6,1984. The shuffle 6f spent. fuel in the fuel pool continued during the month in preparation for refuel of unit 3 reactor vessel. This work was completed on June 15. Lead Test Assembly inspections were completed on June 13. zThis work was conducted by General Electric. The remainder of the month the refuel floor personnel were involved with equipment and system preparations, checkout and installation in-support of cavity and vessel draindowm for jet pu ) nozzle weld overlay.

~ -_.- ._

7 , .

,.e 4 31 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT JUNE 1984 C. Balance of Plant Work continued on "C" Residual Heat Removal (RHR) heat exchanger during the month. Seven tubes were plugged after probolog. All work was completed on June 7 Modification work continued on the diesel generators in an effort to meet the commitment date of August 1 for completion of all eight diesels. The

"?B" and "3A" diesel generators were completed on June 3 and June 10 respectively. The unit 1 & 2 "D" diesel was tagged on June 18 and completed on June 25.

3 Start of modification work on the next diesel generator (unit 1 & 2 "C")

was delayed due to an unscheduled unit 1 trip.

D. Turbine -

Replacement of the four worn wheels on the turbine building crane was com- '

pleted on June 7,1984.

E. Other Mechanical Wo rk 5 - . _

1. Valves 1-55 and 56 -- Both. valves were retested on June 1 and failed.

MDv? valves were repaired and are awaiting retest. Both valvas had EMI-18 (Motor Operator Checks) conducted on June 19,-1984.

~

2. Po730 Head Spray Piping Removal -- This modification is continuing.

. Presently, piping is being cut.

3. P0612 ' Stainless Steel Flex Line Installation -- All hangers for the flex line were completed by June 21. All remaining uork is continuing.

. . - .2 x- - -

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'N O f 32 T

t OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT JUNE 1984 E. Other Mechanical' Work (Continued)

~

4. P0688/690 76-Series Valves - All work was completed on June 6,1984.

5. P0689/691 64-Series Valve Modification to Allow the Flange Side to be Tested - Work is presently delayed pending the receipt of "0" rings to continue work. Expected delivery date is July 14, 1984.

6. P0695 84-Series Valve Modification to Allow the Flange Side to be Tested - This work is continuing. Repair work required on 84-8A is being delayed pending resolution of hold order clearance requirements.

7. P0684 Torus Vacuum Breakers - Work is continuing; awaiting receipt of remaining hinge arms and discs in order to complete this modification.

8. Valve 71-580 -- Repair work is continuing; disk was machined and valve seat is presently being lapped.

9. Valve 69-1 -- Passed Local Leak' Rate Test (LLRT) on June 5,1984.

10. Valves 76-17,18,- and 15 passed LLRT on June 6,1984. _-

11. Valves 74-71, 72, and 73 passed LLRT on June 6,1984. -

12. P0569 Reactor Vent Valves - This work is continuing.

13. P0631 Move Radiation Monitor Element -- All trechanical work was completed June 28, while other work continues.

F. Electrical / Instrumentation

1. Diesel Generators - Completed modifications P0185 Rewiring of Diesel Protective Circuit, P0275 Degraded Voltage' Relay Replacements, and P0585 Speed Sensing Device on "3A," "3B" and "1/2 D" diesels.

. Awaiting outage on "1/2 C" to continue work.

2. P5061 Reroute Conduit and Associated Cables (RHR Instrumentation) That were Cut While Core Drilling for Torus Modification - Work was completed on June 19, 1984.

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-33 '

OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT JUNE'1984 F. ' Electrical / Instrumentation (Continued)

~3. PO479/590 Emergency Lighting - Work is continuing. -

4. LPRM Connections - All new assemblies were connected June 5,1984.

5. P0322/323 Level Transmitters -- Work was delayed due to late arrival

_.'k ' '

of transmitters. Transmitters arrived on site June 14,198'., and it 6-x* 'was then discovered that the compression rinds were missing. Work is c

n pending location and receipt of these rings.-

6. P0284 Acoustic Monitors -- Work is continuing.-

7. P0533 Torus Temperature Devices - Work is continuing. Work cannot be a completed until P0126 is completed (which provides power for checkouts and post modification testing).

8. P3138 RHR Pump Room Cooler Fan Motors - All work on Loop.I RHR is complete. Awaiting outage on Loop II to complete all work activities.

9. . .NRC 79-61B Modifications - Work is continuing. Awaiting setpoints from Engineering-Design to perform SI's on several modifications. -

4

10. EMI 71 -- All unit 3 cycle 5 motors are complete as of June 17, 1984.

11. EMI 7 -- Five breckers remain to be done this outage.

G. Torus Torus work was.as le11ows: '

.1.- .P2124 Restraints to RWCU Piping in Drywell -- Work was completed on'

+

I June .11 4,.1984.

, 2. . . Attached piping suppor:, work continued with 202 complete of 456,

.3. .NRC 79-0? Hanger Inspections - Work continued on inspections and.

, , repairs with-425. of 456 complete. '

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34 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT JUNE' 1984

, H. Plannina and Scheduling

1. Unit 3 cycle 5 planning and scheduling emphasis for the month of June was focused primarily on resequencing the work activities to accomodate jet pump instrument nozzle weld overlay and related tasks (vessel draindown). The unit 3 cycle 5 planning staff is continually evaluating the scheoule so that changes and refinements can be applied as needed.

2. Unit 2 cycle 5 pre-outage planning continues with several major maintenance items and modifications currently being scoped. A preliminary review of unit 2 work items indicates that the outage duration will be far in excess of the scheduled 120 days. Fonmal authorization to reschedule several Nuclear Regulatory Commission (NRC)-related modifications is urgently needed. Although unit 2 may shut-down as early as September 5, the refueling outage start date is scheduled for September 14 after peak.

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TENNESSEE VALLEY AUTHOR 11 Y Browns Ferry Nuclear Plant P..O. Box 2000 Decatur, Alabama 35602 jul111984 Nuclear Regulatory Commission Office of Management Information

.and Program Control Washington, DC- '20555 Gentlemen:

Enclosed is the June 1984 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant Units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY Atw G. T. nes Pla Manager.

Enclosures cc: Director, Region II INPO Records Center Nuclear Regulatory Commission- Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta,'GA 30303 (1 copy) Atlanta, GA 30389 i Director, Office of, Inspection and Enforcement

Nuclear Regulatory Commission Washington,.D. C. 20555 (10 copies)

Mr.~A.'Rubio, Director Electric Power Research Institute P. O. Box 10412 .

Palo Alto, CA-- 94304:

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,  : An Equal Opportunity Employerl-

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